Irradiation surveillance program as applied in Switzerland

Conference · Wed Dec 31 23:00:00 EST 1980 · Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)

OSTI ID:6187057

Njo, D H; Varga, T

Present irradiation surveillance programs are based mainly on Charpy V-notch impact bend specimens. The nil-ducility transition temperature shift as a relative measure of embrittlement is determined from the transition temperature curves. Under the assumption of identical shifts of Charpy V-notch transition curves and the pressure vessel material fracture behavior, the pressure-temperature limits for the reactor pressure vessel are derived. Problems inherent in the use of Charpy V-notch impact bend specimens are discussed and an approach to overcome them presented. The surveillance programs for a pressurized water reactor and boiling water reactor are described.

• Research Organization: Swiss Nucl Saf Div, Wuerenlingen, Switz
• OSTI ID: 6187057
• Report Number(s): CONF-800609-
• Journal Information: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States), Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States); ISSN ASTTA
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
BWR TYPE REACTORS
CHARPY TEST
CONTAINERS
DESTRUCTIVE TESTING
EMBRITTLEMENT
EUROPE
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICAL TESTS
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTORS
STEELS
SWITZERLAND
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE